US5008069A - Device for cooling a heat-generating member - Google Patents

Device for cooling a heat-generating member Download PDF

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Publication number
US5008069A
US5008069A US07/479,418 US47941890A US5008069A US 5008069 A US5008069 A US 5008069A US 47941890 A US47941890 A US 47941890A US 5008069 A US5008069 A US 5008069A
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United States
Prior art keywords
conduit
vessel
liquid
evaporator
nuclear reactor
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Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Fee Related
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US07/479,418
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English (en)
Inventor
Jan Fredell
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Westinghouse Electric Sweden AB
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ABB Atom AB
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Assigned to ABB ATOM AB, A SWEDISH CORP reassignment ABB ATOM AB, A SWEDISH CORP ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: FREDELL, JAN
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a device for cooling of a heat-generating member which is placed in a liquid located in a pressure vessel, which liquid is adapted to serve as a coolant for the heat-generating member.
  • the present invention is specially directed to the case where the heat-generating member consists of a core in a nuclear reactor of the type in which the reactor vessel is arranged in a neutron-absorbing liquid, for example an aqueous solution of boric acid, and the reactor coolant in the lower and upper ends of the reactor is arranged in hydraulic communication with the neutron-absorbing liquid.
  • a coolant flow normally a light water flow
  • the heat contents of the flow being utilized in a steam generator, or other heat exchanger, before the coolant is returned to the reactor vessel for repeated heating in the core.
  • a reactor of such a kind is described, inter alia, in Swedish patent specifications Nos. 7606622-4 and 8102000-0.
  • Operating situations with decay power cooling of the reactor core may occur both with a pressurized pressure vessel and with the vessel pressure-relieved to a pressure which only somewhat exceeds the atmospheric pressure. In certain hypothetical cases the pressure may be almost as great outside the pressure vessel as inside the same. The reason for the pressure relief may be rupture on the pressure vessel or on a pressurized tube connected to the pressure vessel.
  • Operating situations with decay power cooling of the reactor core may also occur, inter alia, in the event of interruption in the supply of electric power or in case of disturbance in the supply of coolant to the reactor core. In the case of decay power cooling of the core, the heat can be removed passively from the core with the aid of a medium flow which may consist of a liquid or steam or a combination thereof.
  • the present invention makes it possible to ensure an efficient cooling of the liquid in the pressure vessel in nearly all operating situations with decay power cooling.
  • the favourable result obtained according to the invention can primarily be attributed to the fact that the cooling of the liquid in the pressure vessel takes place under self-circulation of a flow of liquid and/or of steam of the liquid with any contents of uncondensable gas in a circulation system containing an evaporator arranged in an evaporation pool, and to the fact that a small part of the flow is discharged from the circulation system to a discharge vessel, in which a lower pressure prevails than in the evaporator.
  • FIG. 1 schematically shows a cross section of a nuclear reactor provided with a device according to the invention
  • FIG. 2 shows on an enlarged scale a part of the device according to FIG. 1.
  • the nuclear reactor in FIG. 1 comprises a pressure vessel 1 which is made of prestressed concrete and is provided with overpressure valves 2.
  • a reactor core 3 included in the reactor is placed in its entirety in a reactor vessel 4.
  • the core 3 is arranged in the lower half, usually in the lower fourth of the vessel space 5.
  • the liquid in which the reactor vessel 4 is immersed is neutron-absorbing and in the exemplified case consists of an aqueous solution of boric acid.
  • the core 3 is cooled by a light water flow continuously flowing through the reactor vessel 4, the heat contents of the flow being utilized in a steam generator (not shown in FIG. 1). Water heated in the reactor departs via the conduit 6 to the steam generator and is pumped, after giving off its heat contents, via the conduit 7 back to the reactor.
  • FIG. 1 shows the state of the reactor when a pressure equilibrium between the neutron-absorbing liquid and the reactor coolant, established during normal operation, has been disrupted and the neutron-absorbing liquid has flown into the reactor so that the power of the reactor core 3 has been reduced to the decay power. Above the liquid surface in the pressure vessel 1 a space 12 with gas and/or steam is then often provided.
  • the pressure vessel 1 is adapted to form part of a circulation system for self-circulation of the liquid from the pressure vessel 1 with any contents of steam of the liquid and of uncondensable gas.
  • the self-circulation is brought about by utilizing the property of the liquid to have a higher density at a lower temperature than at a higher temperature.
  • the circulation system comprises an evaporator 14 arranged in an evaporation pool 13, a supply conduit 15 for conducting liquid from a point of connection 15a in the upper part of the pressure vessel 1 to the evaporator 14, and a discharge conduit 16 for conducting liquid from the evaporator 14 to a point of connection 16a, located below the point of connection 15a, on the pressure vessel 1.
  • the evaporation pool 13 may consist of a pool with water. Heat from the evaporation pool 13 is discharged passively by free departure of steam via a conduit 17 to a heat sink 18, which, for example, may consist of the surrounding open air. If the conduit 17 is closed, the heat, as will be described later on, may be discharged via the conduit 19. In certain operating situations, when the liquid level in the pressure vessel 1 may become low and lie below the point of connection 15a, only steam with any contents of uncondensable gas escapes from the vessel 1 via the conduit 15.
  • the discharge conduit 16 at a level above the bottom 16b (FIG. 2), is connected to a discharge vessel (flash tank) 21 by a connecting conduit 20, which only allows a considerably smaller flow than the flow in the circulation system, the discharge vessel 21 being provided with one or more outlets 22a, 23a for gas and steam for maintaining a lower pressure in the discharge vessel 21 than in the evaporator 14.
  • the supply conduit 15 may be connected, at a level above the bottom 15b (FIG. 2), to the discharge vessel 21, by means of a conduit 20a.
  • a heat transport to the discharge vessel 21 is counteracted when the liquid flow in the discharge conduit 16 fills up a minor part of the tube area.
  • Preferably, less than 1% of the flow is diverted through the evaporator 14 to the discharge vessel 21.
  • the primary medium through the evaporator 14 may consist of different contributions of water and steam and any uncondensable gas occurring.
  • the flow, which is passively discharged through the discharge vessel 21, prevents any major accumulation of uncondensable gas on the primary side of the evaporator 14 deteriorating the heat transfer to the evaporator 14.
  • Passive discharge of the flow may take place by connecting the conduit 22 to a heat sink 24, which may, for example, consist of the surrounding open air, whereby the steam and the gas, before departing by themselves, are suitably brought to pass through a gas cleaning system.
  • the discharge of the flow may take place through the conduit 23 to a heat sink 25 placed at a lower level than the discharge vessel 21, for example in the form of a pool of water.
  • this heat sink 25 may communicate with the evaporation pool 13 in order to take up medium from this pool if the tube 17 is closed and overboiling occurs in the pool 13. Any condensed liquid which is collected in the discharge vessel 21 is discharged through the conduit 26 or through the conduit 23 if the conduit 26 is closed.
  • the pressure vessel 1, the evaporation vessel 13 with the evaporator 14, the conduits 15 and 16, the discharge vessel 21 and the heat sink 25 are enclosed, in the illustrated case, in a common prestressed concrete containment 27.
  • a space 28 which is filled with a gas, preferably air or nitrogen. This space is arranged in communication with the heat sink 25 by means of a liquid seal 29.
  • the heat sink 25 is preferably connected to a heat sink (not shown) arranged outside the concrete containment 27, for example the surrounding open atmosphere (via a gas cleaning system) and can thus be said to serve as a temporary heat sink.
  • gas and steam are preferably discharged out through the conduit 22 while at the same time water is discharged out through the conduit 26.
  • the conduit 23 is then closed with the aid of a water seal at the outlet of the conduit into the liquid in the pool 25.
  • the liquid level in the pressure vessel 1 always lies above the point of connection 15a.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
US07/479,418 1989-02-13 1990-02-13 Device for cooling a heat-generating member Expired - Fee Related US5008069A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
SE8900480A SE467028B (sv) 1989-02-13 1989-02-13 Anordning foer resteffektkylning av en kaernreaktorhaerd
SE8900480 1989-02-13

Publications (1)

Publication Number Publication Date
US5008069A true US5008069A (en) 1991-04-16

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Family Applications (1)

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US07/479,418 Expired - Fee Related US5008069A (en) 1989-02-13 1990-02-13 Device for cooling a heat-generating member

Country Status (4)

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US (1) US5008069A (it)
JP (1) JPH02247598A (it)
IT (1) IT1241170B (it)
SE (1) SE467028B (it)

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5158742A (en) * 1991-12-11 1992-10-27 General Electric Company Reactor steam isolation cooling system
US5169595A (en) * 1991-09-03 1992-12-08 General Electric Company Reactor core isolation cooling system
US5282230A (en) * 1992-11-25 1994-01-25 General Electric Company Passive containment cooling system
US5295168A (en) * 1993-04-15 1994-03-15 General Electric Company Pressure suppression containment system
US5301215A (en) * 1992-11-25 1994-04-05 General Electric Company Nuclear reactor building
US5353318A (en) * 1993-05-03 1994-10-04 General Electric Company Pressure suppression system
EP0681300A1 (en) * 1994-05-04 1995-11-08 General Electric Company Pressure suppression system
US5642389A (en) * 1993-04-22 1997-06-24 Siemens Aktiengesellschaft Light water reactor in particular a boiling water reactor with a high degree of inherent safety
US6594333B2 (en) * 2001-11-16 2003-07-15 Japan Nuclear Cycle Development Institute Thermal load reducing system for nuclear reactor vessel
US6618461B2 (en) * 2001-02-12 2003-09-09 General Electric Company Systems and methods to enhance passive containment cooling system
US6718001B2 (en) * 2000-11-15 2004-04-06 Hitachi, Ltd. Nuclear reactor
US7680237B1 (en) * 1998-03-03 2010-03-16 Areva Np Gmbh Containment vessel and method of operating a condenser in a nuclear power plant
US20130051511A1 (en) * 2011-08-25 2013-02-28 Ronald C. Watson Pressurized water reactor with compact passive safety systems

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20220012511A (ko) * 2020-07-23 2022-02-04 한국수력원자력 주식회사 피동보조급수계통의 피동응축탱크 냉각 시스템

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4519978A (en) * 1982-09-22 1985-05-28 Commissariat A L'energie Atomique Secondary heat transfer circuit for a nuclear reactor
US4526742A (en) * 1981-03-30 1985-07-02 Ab Asea-Atom Nuclear reactor plant
US4608224A (en) * 1980-07-04 1986-08-26 Service National Electricite De France Nuclear reactor cooled by a liquid metal
US4643871A (en) * 1979-11-16 1987-02-17 Commissariat A L'energie Atomique Emergency cooling device for a pressurized water reactor core

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4643871A (en) * 1979-11-16 1987-02-17 Commissariat A L'energie Atomique Emergency cooling device for a pressurized water reactor core
US4608224A (en) * 1980-07-04 1986-08-26 Service National Electricite De France Nuclear reactor cooled by a liquid metal
US4526742A (en) * 1981-03-30 1985-07-02 Ab Asea-Atom Nuclear reactor plant
US4519978A (en) * 1982-09-22 1985-05-28 Commissariat A L'energie Atomique Secondary heat transfer circuit for a nuclear reactor

Cited By (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5169595A (en) * 1991-09-03 1992-12-08 General Electric Company Reactor core isolation cooling system
US5158742A (en) * 1991-12-11 1992-10-27 General Electric Company Reactor steam isolation cooling system
US5301215A (en) * 1992-11-25 1994-04-05 General Electric Company Nuclear reactor building
US5282230A (en) * 1992-11-25 1994-01-25 General Electric Company Passive containment cooling system
EP0620560A1 (en) * 1993-04-15 1994-10-19 General Electric Company Pressure suppression containment system
US5295168A (en) * 1993-04-15 1994-03-15 General Electric Company Pressure suppression containment system
US5642389A (en) * 1993-04-22 1997-06-24 Siemens Aktiengesellschaft Light water reactor in particular a boiling water reactor with a high degree of inherent safety
US5353318A (en) * 1993-05-03 1994-10-04 General Electric Company Pressure suppression system
EP0681300A1 (en) * 1994-05-04 1995-11-08 General Electric Company Pressure suppression system
US7680237B1 (en) * 1998-03-03 2010-03-16 Areva Np Gmbh Containment vessel and method of operating a condenser in a nuclear power plant
US6718001B2 (en) * 2000-11-15 2004-04-06 Hitachi, Ltd. Nuclear reactor
US6618461B2 (en) * 2001-02-12 2003-09-09 General Electric Company Systems and methods to enhance passive containment cooling system
US6594333B2 (en) * 2001-11-16 2003-07-15 Japan Nuclear Cycle Development Institute Thermal load reducing system for nuclear reactor vessel
US20130051511A1 (en) * 2011-08-25 2013-02-28 Ronald C. Watson Pressurized water reactor with compact passive safety systems
US8867690B2 (en) * 2011-08-25 2014-10-21 Babcock & Wilcox Mpower, Inc. Pressurized water reactor with compact passive safety systems

Also Published As

Publication number Publication date
IT1241170B (it) 1993-12-29
IT9067101A1 (it) 1990-08-14
SE8900480L (sv) 1990-08-14
IT9067101A0 (it) 1990-02-12
SE8900480D0 (sv) 1989-02-13
SE467028B (sv) 1992-05-11
JPH02247598A (ja) 1990-10-03

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Effective date: 19990416

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Free format text: PATENT EXPIRED DUE TO NONPAYMENT OF MAINTENANCE FEES UNDER 37 CFR 1.362